Nuclear Regulatory Commission 2009 – Federal Register Recent Federal Regulation Documents
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Notice of Opportunity for Public Comment on the Proposed Model Safety Evaluation for Plant-Specific Adoption of Technical Specification Task Force Traveler-493, Revision 4, “Clarify Application of Setpoint Methodology for LSSS Functions”
The NRC is requesting public comment on the enclosed proposed model application, model no significant hazards consideration determination, and model safety evaluation for plant-specific adoption of Technical Specification Task Force (TSTF) Traveler-493, Revision 4, ``Clarify Application of Setpoint Methodology for LSSS Functions.'' The TSTF Traveler-493, Revision 4, is available in the Agencywide Documents Access and Management System (ADAMS) under Accession Number ML092150990. The proposed changes revise Standard Technical Specifications (STS) with respect to limiting safety system settings (LSSSs) assessed during periodic testing and calibration of instrumentation that may have an adverse effect on equipment operability. This model safety evaluation will facilitate expedited approval of plant-specific adoption of TSTF Traveler-493, Revision 4.
Office of New Reactors; Final Interim Staff Guidance on Finalizing Licensing Basis Information
The NRC is issuing its Final Interim Staff Guidance (ISG) DC/ COL-ISG-011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092890623). This ISG is to clarify the NRC staff position on finalizing licensing basis information at a point during the licensing review, a so-called freeze point, and the control of licensing basis information during and following the initial review of applications for design certifications (DCs) or combined licenses (COLs). The NRC staff issues COL/DC-ISGs to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for DCs and COLs by the Office of New Reactors (NRO). The NRC staff intends to incorporate the final approved DC/COL-ISG-011 into the next revision of Regulatory Guide 1.206, ``Combined License Applications for Nuclear Power Plants.''
Draft Safety Culture Policy Statement: Request for Public Comments
The NRC is issuing a draft policy statement that sets forth the Commission's expectation that all licensees and certificate holders \1\ establish and maintain a positive safety culture that protects public health and safety and the common defense and security when carrying out licensed activities. The Commission defines safety culture as that assembly of characteristics, attitudes, and behaviors in organizations and individuals which establishes that as an overriding priority, nuclear safety and security issues \2\ receive the attention warranted by their significance. The Commission also considers nuclear safety and security issues to be equally important in a positive safety culture. The importance of treating safety and security in an equal manner within NRC's regulatory framework is clearly evident in our mission and strategic goals. Experience has shown that certain organizational characteristics and personnel attitudes and behaviors are present in a positive safety culture. These include, but are not limited to, individuals demonstrating ownership and personal responsibility for maintaining safety and security in their day-to-day work activities; the implementation of processes for planning and controlling work activities such that safety and security are maintained; a work environment in which personnel feel free to raise safety and security concerns without fear of retaliation; prompt and thorough identification, evaluation, and resolution of nuclear safety and security issues commensurate with their significance; the availability of the resources needed to ensure that safety and security are maintained; decision-making processes that protect safety and security; clearly defined roles and responsibilities for maintaining safety and security; and the seeking out and implementation of opportunities to improve safety and security. The NRC expects its licensees and certificate holders to foster these characteristics, attitudes, and behaviors in their organizations and among individuals who are overseeing or performing regulated activities commensurate with the safety and security significance of their activities and the nature and complexity of their organization and functions.
Agency Information Collection Activities: Proposed Collection; Comment Request
The NRC invites public comment about our intention to request the OMB's approval for renewal of an existing information collection that is summarized below. We are required to publish this notice in the Federal Register under the provisions of the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35).
Office of New Reactors; Interim Staff Guidance on Design Reliability Assurance Program; Section 17.4 of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG-0800)
The NRC staff is soliciting public comment on its proposed Interim Staff Guidance (ISG) DC/COL-ISG-018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092290791). This ISG revises the guidance provided to the staff in Section 17.4, ``Reliability Assurance Program'' of NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,'' March 2007 (SRP). This ISG revises the review responsibilities and further clarifies the acceptance criteria and evaluation findings contained in SRP Section 17.4 in support of the NRC reviews of the design certification (DC) and combined license (COL) applications. The NRC staff issues DC/COL-ISGs to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for DCs and COLs by the Office of New Reactors. The NRC staff intends to incorporate the final approved DC/COL-ISG-018 into the next revision of NUREG-0800, SRP Section 17.4 and Regulatory Guide (RG) 1.206, ``Combined License Applications for Nuclear Power Plants (LWR Edition),'' June 2007.
Office of New Reactors; Interim Staff Guidance on Post-Combined License Commitments
The NRC is soliciting public comment on its Proposed Interim Staff Guidance (ISG) ESP/DC/COL-ISG-015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091671355). The purpose of this ISG is to modify and provide early site permit (ESP), design certification (DC) and combined license (COL) applicants additional clarity and guidance for the application of Section C.III.4 of Regulatory Guide (RG) 1.206. In addition, the ISG provides additional clarity to the guidance in NUREG-0800, Standard Review Plan Chapter 1.0, for NRC review of DC and COL applications. While reviewing DC and COL applications, the NRC staff determined that the guidance in Section C.III.4 of RG 1.206 on COL information items that cannot be resolved before the issuance of a license needed some additional clarification and guidance. In addition, it was determined that referring to this category of COL information items as ``COL Holder'' items is inappropriate. Specific guidance for determining which of the commitment types (i.e., inspection, test, analysis, and acceptance criteria, license condition, and final safety analysis report commitment) was the most appropriate for these COL information items was considered necessary, along with examples for clarification, for common understanding by applicants preparing their COL applications and NRC staff reviewing these COL applications. The NRC staff issues ISGs to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications by the Office of New Reactors. The NRC staff also intends to incorporate the approved ESP/DC/COL-ISG-015 into the next revision of RG 1.206 and related guidance documents.
Appointments to Performance Review Boards for Senior Executive Service
The U.S. Nuclear Regulatory Commission (NRC) has announced the following appointments to the NRC Performance Review Boards.
Agency Information Collection Activities: Submission for the Office of Management and Budget (OMB) Review; Comment Request
The NRC has recently submitted to OMB for review the following proposal for the collection of information under the provisions of the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35). The NRC hereby informs potential respondents that an agency may not conduct or sponsor, and that a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number. The NRC published a Federal Register Notice with a 60-day comment period on this information collection on August 14, 2009.
Industry Codes and Standards; Amended Requirements; Confirmation of Effective Date
The Nuclear Regulatory Commission (NRC) is confirming the effective date of October 19, 2009, for the direct final rule that was published in the Federal Register on August 5, 2009. This direct final rule amended the NRC's regulations on governing vessel head inspection requirements. This amendment revised the upper range of the percentage of axial flaws permitted in a specimen set used for the qualification of nondestructive examination systems (procedures, personnel and equipment), which are used in the performance of inservice inspection (ISI) of pressurized water reactor (PWR) upper vessel head penetrations. This amendment was made as a result of the withdrawal of a stakeholder's recommendation necessitated by a typographical error in the original recommendation with respect to the maximum percentage of flaws that should be oriented axially.
Office of New Reactors; Interim Staff Guidance on Implementation of a Seismic Margin Analysis for New Reactors Based on Probabilistic Risk Assessment
The NRC staff is soliciting public comment on its Proposed Interim Staff Guidance (ISG) DC/COL-ISG-020 titled ``Interim Staff Guidance on Implementation of a Seismic Margin Analysis for New Reactors Based on Probabilistic Risk Assessment, ``(Agencywide Documents Access and Management System (ADAMS) Accession No. ML092650342). This ISG supplements the guidance provided to the staff in Section 19.0 of NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,'' issued March 2007 and DC/COL-ISG-03, ``Probabilistic Risk Assessment Information to Support Design Certification and Combined License Applications,'' dated June 11, 2008 (ADAMS Accession No. ML081430087) concerning the review of probabilistic risk assessment (PRA) information and severe accident assessments submitted to support design certification (DC) and combined license (COL) applications. The NRC staff intends to incorporate the final approved DC/COL-ISG-020 into the next revision of SRP Section 19.0 and Regulatory Guide 1.206, ``Combined License Applications for Nuclear Power Plants (LWR Edition),'' June 2007.
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